In deuterium-tritium fusion reactors currently under design, the production of tritium is accomplished by utilizing a lithium-bearing blanket. Lithium metal is presently the leading candidate for the blanket material, although molten Li$sub 2$BeF$sub 4$, solid Li--Al (50-50 at. percent) alloy and other lithium-containing materials are distinct possibilities. This paper summarizes progress of ongoing studies of the thermodynamics of some of these lithium containing systems. The individual solubilities of hydrogen, deuterium, and tritium in lithium as a function of temperature (700 to 1000$sup 0$C) and pressure are presented. Recent work with the solid alloy Li--Al (50-50 at. percent) has shown that the tritium solubility between 400 and 600$...
An attractive feature of using liquid lithium as the breeder and coolant in fusion blankets is that ...
An attractive feature of using liquid lithium as the breeder and coolant in fusion blankets is that ...
From 5th symposium on engineering problems of fusion research; Princeton, New Jersey, USA (6 Nov 197...
From joint meeting of the American Nuclear Society and the Atomic Industrial Forum and Nuclear Energ...
This paper described measurements of (1) the distribution of tritium and helium throughout both phas...
Physicochemical and thermodynamic studies of liquid-lithium-containing systems have continued. Press...
The available thermodynamic information is reviewed for three categories of materials that meet esse...
The feasibility of fusion reactor blankets with low residual activity is examined. Several designs a...
The program is concerned with investigating the chemistry of those compounds and alloys of lithium w...
Several methods for tritium recovery from liquid lithium, Li-Pb eutectic alloy, aqueous salt solutio...
Hydrogen release characteristics of Al-Li alloys at room temperature were examined by liquid scintil...
Tritium, one fuel component of the fusion reactor is bred from the reactors blanket material lithium...
A major concern in fusion reactor design is possible hydrogen-isotope-induced embrittlement of struc...
An attractive feature of using liquid lithium as the breeder and coolant in fusion blankets is that ...
As lithium has grown in popularity as a plasma-facing material, efforts have been placed on examinin...
An attractive feature of using liquid lithium as the breeder and coolant in fusion blankets is that ...
An attractive feature of using liquid lithium as the breeder and coolant in fusion blankets is that ...
From 5th symposium on engineering problems of fusion research; Princeton, New Jersey, USA (6 Nov 197...
From joint meeting of the American Nuclear Society and the Atomic Industrial Forum and Nuclear Energ...
This paper described measurements of (1) the distribution of tritium and helium throughout both phas...
Physicochemical and thermodynamic studies of liquid-lithium-containing systems have continued. Press...
The available thermodynamic information is reviewed for three categories of materials that meet esse...
The feasibility of fusion reactor blankets with low residual activity is examined. Several designs a...
The program is concerned with investigating the chemistry of those compounds and alloys of lithium w...
Several methods for tritium recovery from liquid lithium, Li-Pb eutectic alloy, aqueous salt solutio...
Hydrogen release characteristics of Al-Li alloys at room temperature were examined by liquid scintil...
Tritium, one fuel component of the fusion reactor is bred from the reactors blanket material lithium...
A major concern in fusion reactor design is possible hydrogen-isotope-induced embrittlement of struc...
An attractive feature of using liquid lithium as the breeder and coolant in fusion blankets is that ...
As lithium has grown in popularity as a plasma-facing material, efforts have been placed on examinin...
An attractive feature of using liquid lithium as the breeder and coolant in fusion blankets is that ...
An attractive feature of using liquid lithium as the breeder and coolant in fusion blankets is that ...
From 5th symposium on engineering problems of fusion research; Princeton, New Jersey, USA (6 Nov 197...